ML20087J432

From kanterella
Jump to navigation Jump to search
Amend 53 to License NPF-4,revising Tech Spec Table 4.3-2 by Removing Requirement for Surveillance in Mode 4 for Auxiliary Feedwater Pump Actuation Signals
ML20087J432
Person / Time
Site: North Anna 
Issue date: 03/06/1984
From: John Miller
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20087J435 List:
References
NUDOCS 8403220212
Download: ML20087J432 (5)


Text

_ _ _ _ - _ _ _ _ _ - - _ _ - _ _

/

R Af 0g"[

A UNITED STATES y j 3m o,h NUCLEAR REGULATORY COMMISSION

/g, p

WASHINGTON, D. C. 20555 VIRGINIA ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRIC COOPERATIVE DOCKET NO. 50-338 NORTH ANNA POWER STATION, UNIT N0. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 53 License No. NPF-4 1.

The Nuclear Regulatory Comission (the Comission) has found that:

A.

The application for amendment by Virginia Electric and Power Company (the licensee) dated November 15, 1983, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations set forth in 10 CFR i

Chapter I; 1

l B.

The facility will operate in conformity with the application, j

the provisions of the Act, and the rules and regulations of the Comission; 1

C.

There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied, i

f l

8403220212 840306 PDR ADOCK 05000338 P

PDR

' 2.

Accordingly, the license is amended by changes to the Technical Speci-fications as indicated in the attachment to this license amendment, and paragraph 2.0.(2) of Facility Operating License No. NPF-4 is hereby amended to read as follows:

I (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 53, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effecti<e as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION s y'. [

I James R. Miller, Chief Operating Reactors Branch #3 1

Division of Licensing j

1

Attachment:

1 Changes to the Technical Specifications Date of Issuance: March 6, 1984

=.

_.. - _... =_ _ _ _ -

~

d i

ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 53 TO FACILITY OPERATING LICENSE NO. NPF-4 1

DOCKET NO. 50-338 Replace the following page of the Appendix "A" Technical Specifications with the enclosed page as indicated.

The revised page is identified by Amendment number and contains vertical lines indicating the area of change.

l The corresponding overleaf page is provided to maintain document completness.

j Page 3/4 3-33 I

d

..s 7

m,.

u--.i v

r.

==O$

TABLE 4.3-2 (Continued) 3=

N ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS 2q CHANNEL MODES IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE

~

FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED 5.

TURBINE TRIP AND FEEDWATER ISOLATION l

a.

Steam Generator Water S

R M

1, 2, 3 Level--High-High 6.

AUXILIARY FEEDWATER PUMPS a.

Manual N. A.

N. A.

M(1) 1, 2, 3 b.

Automatic Actuation N. A.

N. A.

M(2) 1, 2, 3 u,,

]s Logic c.

Steam Generator Water S

R H

1, 2, 3 l

62 Level--Low-Low d.

S.I.

See 1 above (all S.I. Surveillance Requirements) e.

Station Blackout N. A.

R N. A.

1, 2, 3 l

f.

Main Feedwater Pump N. A.

N. A.

R 1, 2 Trip k

7.

LOSS OF POWER

,3 4.16 KV Emergency Bus

?>

a.

Loss of Voltage N. A.

R M(2) 1, 2, 3

,o b.

Degraded Voltage N. A.

R M(2) 1, 2, 3 k.E

TABLE 4.3-2 (Continued)

TABLE NOTATION (1) Manual actuation switches shall be tested at least once per 18 months during shutdown. All other circuitry associated with manual safeguards actuation shall receive a CHANNEL FUNCTIONAL TEST at least once every other 31 days.

(2) Each train or logic channel shall be tested at least every other 31 days.

(3) The CHANNEL FUNCTIONAL TEST shall include exercising the transmitter by applying either a vacuum or pressure to the appropriate side of the transmitter.

NORTH ANNA - UNIT 1 3/4 3-34 e

.-